Published April 1997
| Version v1
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The LBB methodology application results performed on the safety related piping of NPP V-1 in Jaslovske Bohunice
Description
A broad overview of the leak before break (LBB) application to the Slovakian V-1 nuclear power plant is presented in the paper. LBB was applied to the primary cooling circuit and surge lines of both WWER 440 type units, and also used to assess the integrity of safety related piping in the feed water and main steam systems. Experiments and calculations performed included analyses of stresses, material mechanical properties, corrosion, fatigue damage, stability of heavy component supports, water hammer, and leak rates. A list of analysis results and recommendations are included in the paper
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the seminar on leak before break in reactor piping and vessels
- Imprint Pagination
- 773 p.
- Journal Page Range
- p. 533-540.
- Report number
- NUREG/CP--0155
Conference
- Title
- Seminar on leak before break in reactor piping and vessels.
- Dates
- 9-11 Oct 1995.
- Place
- Lyon (France).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28076036
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOHUNICE V-1 REACTOR; FEEDWATER; LEAKS; PIPES; PRIMARY COOLANT CIRCUITS; SAFETY ANALYSIS; STEAM SYSTEMS
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Secondary number(s)
- CONF-9510432--.